国胜核电站控制室围护结构未过滤空气泄漏分析

IF 0.4 4区 工程技术 Q4 NUCLEAR SCIENCE & TECHNOLOGY
Kerntechnik Pub Date : 2023-08-24 DOI:10.1515/kern-2023-0044
Yu-Ching Tsai, Chunqing Yang
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引用次数: 0

摘要

摘要核电站控制室围护结构在各种事故中起着至关重要的作用。只有保证了CRE的可居住性,操作人员才能在危险化学品或放射性气体释放的事故中安全关闭反应堆。本研究以台湾国胜核电厂(NPP)为研究对象,采用示踪气体技术进行泄漏试验,并在6个不同的暖通空调系统(HVAC)组合下进行泄漏试验。试验结果表明,各增压模式下的未过滤渗速范围为0.063 m3/s ~ 0.098 m3/s,均在0.212 m3/s的验收标准范围内。对于隔离模式,未过滤的漏率范围为0.240 m3/s ~ 0.321 m3/s,均在0.944 m3/s的可接受标准范围内。测试结果为改进CRE的漏洞提供了有用的信息。它还表明,如果临界边界(如通风系统的负微分部分)仍然密封良好,则CRE相对于其周围环境的正压差的降低并不一定会增加CRE的未过滤泄漏率。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Unfiltered air inleakage analysis of the control room envelope of Kuosheng nuclear power plant
Abstract The control room envelope (CRE) of a nuclear power plant is quite important during all kinds of the accidents. Only with the guaranteed habitability of the CRE, the operators can shut down the reactor safely during an accident with the release of hazardous chemicals or radioactive gases. In this study, Kuosheng nuclear power plant (NPP) in Taiwan had performed the inleakage test by using tracer gas technique, and six cases with different heating, ventilation and air conditioning system (HVAC) lineups were tested in this study. The test results showed that the unfiltered inleakage rate for the pressurization modes ranged from 0.063 m3/s to 0.098 m3/s and were all within the acceptance criteria of 0.212 m3/s. For the isolation modes, the unfiltered inleakage rate ranged from 0.240 m3/s to 0.321 m3/s and were still within the acceptance criteria of 0.944 m3/s. The test result provided useful information to improve the vulnerability of the CRE. It also showed that a decrease in the positive differential pressure of the CRE relative to its surroundings did not inevitably increase the unfiltered inleakage rate of the CRE if the critical boundary, such as the negative differential portions of the ventilation system, were still well sealed.
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来源期刊
Kerntechnik
Kerntechnik 工程技术-核科学技术
CiteScore
0.90
自引率
20.00%
发文量
72
审稿时长
6-12 weeks
期刊介绍: Kerntechnik is an independent journal for nuclear engineering (including design, operation, safety and economics of nuclear power stations, research reactors and simulators), energy systems, radiation (ionizing radiation in industry, medicine and research) and radiological protection (biological effects of ionizing radiation, the system of protection for occupational, medical and public exposures, the assessment of doses, operational protection and safety programs, management of radioactive wastes, decommissioning and regulatory requirements).
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